neutron cross section

In general, the neutron cross-section is an effective area that quantifies the likelihood of certain interaction between an incident neutron 

The neutron cross sections provide information about what happens to the neutrons when they pass with atoms of the material. For this reason, 

4/12 · Gadolinium-157 has the highest thermal-neutron capture cross-section among any stable nuclide.Based on my layman's understanding of neutron capture – particularly the fact that (I assume) neutrons don't much care about electron shells – I would have guessed that neutron capture cross-section would be proportional to either:

During the Manhattan Project, physicists needed to predict the probability of a free neutron striking the nucleus of a fissionable substance, forcing the nucleus to undergo fission. The area within which fission would be expected to occur, is defined to be the "fission cross-section." Fission is not the only potential interaction between

3.2 MODULE OBJECTIVES After studying this module, you should be able to: i) List the various reactions that a neutron can undergo during its lifetime. ii) Define the microscopic reaction

For most nuclides the scattering lengths and scattering cross sections are independent of the incident neutron wave vector kin the thermal neutron region, 

Straight black line: 3 He neutron cross section as a from publication: Characterization of a thermal neutron beam monitor based on gas electron multiplier 

1 day ago · The NGATLAS contains neutron capture cross sections in the range 10-5eV - 20MeV as evaluated and compiled in recent activation libraries. Numerical values of (n,g) cross

In most cases, the absorption cross section, \ (\sigma_ {\rm a}\), of thermal neutrons is inversely proportional to the neutron velocity. In other words, the absorption is proportional to the

I. THERMAL CROSS SECTIONS. A. Capture, Absorption, Fission, and Total Cross Sections. The total neutron cross section can be written as the sum of partial 

PDF | We report a new measurement of the total cross section of polyethylene at room temperature, for neutrons with energies between 10−3